Virtual Engineering of a Fusion Reactor: Application to Divertor Design, Manufacture, and Testing

被引:12
作者
Barrett, Thomas R. [1 ]
Evans, Llion M. [1 ]
Fursdon, Mike [1 ]
Domptail, Fred [1 ]
McIntosh, Simon C. [1 ,2 ]
Iglesias, Daniel [1 ]
Surrey, Elizabeth [1 ]
机构
[1] Culham Sci Ctr, CCFE, Abingdon OX14 3DB, Oxon, England
[2] ITER Org, F-13067 St Paul Les Durance, France
基金
英国工程与自然科学研究理事会;
关键词
Image-based finite-element method (FEM); thermal break; virtual engineering; water-cooled divertor; PROGRESS; TARGET;
D O I
10.1109/TPS.2018.2856888
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Virtual engineering is being widely adopted in diverse technical fields and has the potential to accelerate the realization of tokamak fusion energy. In this paper, we demonstrate, for the first time, the use of virtual engineering techniques to enhance the development cycle of a water-cooled divertor plasma facing component. The divertor concept under development is the thermal break, which aims to increase heat flux limits and DEMO-relevance by alleviating the high thermal mismatch stress between a tungsten monoblock and a copper alloy cooling pipe. Response surface-based design search and optimization is used to explore the potential of the concept and to inform the design of a high-heat-flux (HHF) mock-up. In developing a brazing manufacturing procedure, computed tomography scanning and subsequent image-based finite-element modeling revealed a defective joining process which would result in unacceptable divertor performance. The same techniques were used to develop an improved brazing procedure that was used to manufacture the mock-ups. A production defect was discovered by ultrasonic qualification testing, but a "virtual twin" model confirmed the acceptable performance of the mock-up under HHF. Indeed, all mock-ups were then subjected to at least 100 cycles of 20 MW/m(2) HHF testing, with no signs of damage. The development of these virtual engineering and modeling techniques will facilitate criteria for design and component rejection, and in future enable predictive maintenance of components in service. Practical trials and experiments will remain essential to complement and validate simulations.
引用
收藏
页码:889 / 896
页数:8
相关论文
共 14 条
  • [1] [Anonymous], 2012, ITERG74MA8010528W02
  • [2] Enhancing the DEMO divertor target by interlayer engineering
    Barrett, T. R.
    McIntosh, S. C.
    Fursdon, M.
    Hancock, D.
    Timmis, W.
    Coleman, M.
    Rieth, M.
    Reiser, J.
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1216 - 1220
  • [3] Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components
    Barrett, Thomas R.
    Ellwood, G.
    Perez, G.
    Kovari, M.
    Fursdon, M.
    Domptail, F.
    Kirk, S.
    McIntosh, S. C.
    Roberts, S.
    Zheng, S.
    Boccaccini, L. V.
    You, J. -H.
    Bachmann, C.
    Reiser, J.
    Rieth, M.
    Visca, E.
    Mazzone, G.
    Arbeiter, F.
    Domalapally, P. K.
    [J]. FUSION ENGINEERING AND DESIGN, 2016, 109 : 917 - 924
  • [4] Transient thermal finite element analysis of CFC-Cu ITER monoblock using X-ray tomography data
    Evans, Ll. M.
    Margetts, L.
    Casalegno, V.
    Lever, L. M.
    Bushell, J.
    Lowe, T.
    Wallwork, A.
    Young, P.
    Lindemann, A.
    Schmidt, M.
    Mummery, P. M.
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 100 : 100 - 111
  • [5] The development and testing of the thermal break divertor monoblock target design delivering 20 MWm-2 heat load capability
    Fursdon, M.
    Barrett, T.
    Domptail, F.
    Evans, L. I. M.
    Luzginova, N.
    Greuner, N. H.
    You, J-H
    Li, M.
    Richou, M.
    Gallay, F.
    Visca, E.
    [J]. PHYSICA SCRIPTA, 2017, T170
  • [6] High heat flux facility GLADIS: Operational characteristics and results of W7-X pre-series target tests
    Greuner, H.
    Boeswirth, B.
    Boscary, J.
    McNeely, P.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) : 1444 - 1448
  • [7] ITER tungsten divertor design development and qualification program
    Hirai, T.
    Escourbiac, F.
    Carpentier-Chouchana, S.
    Fedosov, A.
    Ferrand, L.
    Jokinen, T.
    Komarov, V.
    Kukushkin, A.
    Merola, M.
    Mitteau, R.
    Pitts, R. A.
    Shu, W.
    Sugihara, M.
    Riccardi, B.
    Suzuki, S.
    Villari, R.
    [J]. FUSION ENGINEERING AND DESIGN, 2013, 88 (9-10) : 1798 - 1801
  • [8] Iglesias D., 2016, 29 S FUS TECHN SOFT
  • [9] Virtual engineering in design and manufacturing
    Lemu, Hirpa
    [J]. ADVANCES IN MANUFACTURING, 2014, 2 (04) : 289 - 294
  • [10] Interpretation of the deep cracking phenomenon of tungsten monoblock targets observed in high-heat-flux fatigue tests at 20 MW/m2
    Li, Muyuan
    You, Jeong-Ha
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 101 : 1 - 8